83-Bi-209 JAEA EVAL-MAR19 N.Iwamoto DIST-DEC21 20190325 ----JENDL-5 MATERIAL 8325 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 2010-03 Resonace parameters were evaluated by N.Iwamoto. 2019-03 Evaluated with CCONE code by N.Iwamoto. 2020-10 Energies of discrete primary photons were corrected. 21-11 above 20 MeV, JENDL-4.0/HE merged by O.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto 21-12 JENDL-5rc1 revised by N.Iwamoto (MF33/MT1,2,102) Added the data below 200 keV (MF34/MT2) Revised MF= 1 General information MT=451 Descriptive data and directory MF= 2 Resonance parameters MT=151 Resolved and unresolved resonances Resolved resonance region (MLBW formula) : below 200 keV Resonance parameters were taken from JENDL-4.0. MF= 3 Neutron cross sections MT= 1 Total cross section Calculated with CCONE code /1/ and base on experimental data. MT= 2 Elastic scattering cross section Obtained by subtracting non-elastic cross sections from total cross sections. MT=4,51-91 (n,n') cross section Calculated with CCONE code /1/. MT= 16 (n,2n) cross section Calculated with CCONE code /1/. MT= 17 (n,3n) cross section Calculated with CCONE code /1/. MT= 22 (n,na) cross section Calculated with CCONE code /1/. MT= 28 (n,np) cross section Calculated with CCONE code /1/. MT= 32 (n,nd) cross section Calculated with CCONE code /1/. MT= 33 (n,nt) cross section Calculated with CCONE code /1/. MT= 41 (n,2np) cross section Calculated with CCONE code /1/. MT=102 Capture cross section Calculated with CCONE code /1/. MT=103,600-649 (n,p) cross section Calculated with CCONE code /1/. MT=104,650-699 (n,d) cross section Calculated with CCONE code /1/. MT=105,700-749 (n,t) cross section Calculated with CCONE code /1/. MT=106,750-799 (n,He3) cross section Calculated with CCONE code /1/. MT=107,800-849 (n,a) cross section Calculated with CCONE code /1/. MF= 4 Angular distributions of secondary particles MT= 2 Elastic scattering Calculated with CCONE code /1/. MF= 6 Energy-angle distributions of emitted particles MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 17 (n,3n) reaction Calculated with CCONE code /1/. MT= 22 (n,na) reaction Calculated with CCONE code /1/. MT= 28 (n,np) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 33 (n,nt) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) reaction Calculated with CCONE code /1/. MT=51-91 (n,n') reaction Calculated with CCONE code /1/. MT=102 Capture reaction Calculated with CCONE code /1/. MT=600-649 (n,p) reaction Calculated with CCONE code /1/. MT=650-699 (n,d) reaction Calculated with CCONE code /1/. MT=700-749 (n,t) reaction Calculated with CCONE code /1/. MT=750-799 (n,He3) reaction Calculated with CCONE code /1/. MT=800-849 (n,a) reaction Calculated with CCONE code /1/. MF= 8 Information on decay data MT=4 (n,n') reaction Decay chain is given in the decay data file. MT= 16 (n,2n) reaction Decay chain is given in the decay data file. MT= 17 (n,3n) reaction Decay chain is given in the decay data file. MT= 22 (n,na) reaction Decay chain is given in the decay data file. MT= 28 (n,np) reaction Decay chain is given in the decay data file. MT= 32 (n,nd) reaction Decay chain is given in the decay data file. MT= 33 (n,nt) reaction Decay chain is given in the decay data file. MT= 41 (n,2np) reaction Decay chain is given in the decay data file. MT=102 Capture reaction Decay chain is given in the decay data file. MT=103 (n,p) reaction Decay chain is given in the decay data file. MT=104 (n,d) reaction Decay chain is given in the decay data file. MT=105 (n,t) reaction Decay chain is given in the decay data file. MT=106 (n,He3) reaction Decay chain is given in the decay data file. MT=107 (n,a) reaction Decay chain is given in the decay data file. MF= 9 Isomeric branching ratios MT=102 Capture reaction Calculated with CCONE code /1/. MT=107 (n,a) reaction Calculated with CCONE code /1/. MF=10 Nuclide production cross sections MT= 16 (n,2n) reaction Calculated with CCONE code /1/. MT= 32 (n,nd) reaction Calculated with CCONE code /1/. MT= 41 (n,2np) reaction Calculated with CCONE code /1/. MT=105 (n,t) reaction Calculated with CCONE code /1/. MT=106 (n,He3) reaction Calculated with CCONE code /1/. MF=33 Covariances of neutron cross sections Covariance data were basically evaluated with CCONE code/1/ and KALMAN code/6/. Evaluated data with the other methods are described bellow. MT= 1 Total cross section 1.0e-5 eV to 200 keV(RRR): given by a sum of the covariance data of the elastic scattering and the neutron capture cross sections. 200 keV to 20 MeV: obtained by the CCONE-KALMAN. MT= 2 Elastic scattering cross sections 1.0e-5 eV to 200 keV(RRR): obtained by the kernel approximation/7/. 200 keV to 20 MeV: obtained by the CCONE-KALMAN. MT=102 Capture cross section 1.0e-5 eV to 200 keV(RRR): obtained by the kernel approximation/7/. 200 keV to 20 MeV: obtained by the CCONE-KALMAN. MF=34 Covariances for Angular Distributions MT= 2 Elastic scattering Obtained by the CCONE-KALMAN. ------------------------------------------------------------------ nuclear model calculation with CCONE code /1/ ------------------------------------------------------------------ * Optical model potentials neutron : A.J.Koning and J.P.Delaroche/2/ proton : A.J.Koning and J.P.Delaroche/2/ deuteron: folding OMP, A.J.Koning and J.P.Delaroche/2/ triton : folding OMP, A.J.Koning and J.P.Delaroche/2/ He-3 : folding OMP, A.J.Koning and J.P.Delaroche/2/ alpha : J.R.Huizenga and G.Igo/8/ * Level scheme of Bi-209 ----------------------- No. Ex(MeV) J PI ----------------------- 0 0.000000 9/2 - 1 0.896290 7/2 - 2 1.608580 13/2 + 3 2.442860 1/2 + 4 2.492820 3/2 + 5 2.564160 9/2 + 6 2.583070 7/2 + 7 2.599900 11/2 + 8 2.600920 13/2 + 9 2.617310 5/2 + 10 2.741050 15/2 + 11 2.766610 3/2 + 12 2.826190 5/2 - 13 2.845140 1/2 + 14 2.916570 1/2 + 15 2.955870 3/2 + 16 2.986790 19/2 + 17 3.038870 5/2 + 18 3.090080 7/2 + 19 3.119540 3/2 - 20 3.132960 11/2 + 21 3.135770 15/2 + 22 3.152830 9/2 + 23 3.154060 17/2 + 24 3.159280 3/2 + 25 3.169070 13/2 + 26 3.197440 3/2 + 27 3.211840 17/2 + 28 3.221580 5/2 + 29 3.269600 5/2 + 30 3.311150 9/2 + 31 3.354700 3/2 + 32 3.362010 7/2 + 33 3.378160 9/2 + 34 3.394300 15/2 + 35 3.406210 13/2 + 36 3.450300 7/2 + 37 3.464120 11/2 + 38 3.467670 19/2 + 39 3.486920 19/2 + 40 3.489850 7/2 - ----------------------- * Level density parameters (Gilbert-Cameron model/3/) Energy dependent parameters of Mengoni-Nakajima/4/ were used. --------------------------------------------------------- a* Pair Eshell T E0 Ematch Elv_max 1/MeV MeV MeV MeV MeV MeV MeV --------------------------------------------------------- Bi-210 24.293 0.000 -7.610 0.781 -1.912 10.773 0.583 Bi-209 24.196 0.830 -8.531 0.609 1.146 4.371 3.490 Bi-208 24.100 0.000 -8.264 0.741 -1.129 8.493 1.095 Bi-207 24.003 0.834 -7.191 0.727 -0.807 9.100 1.770 Pb-209 22.018 0.830 -8.607 0.659 1.264 4.675 3.681 Pb-208 24.100 1.664 -9.961 0.745 1.746 9.649 4.447 Pb-207 24.003 0.834 -9.554 0.701 1.099 6.758 3.726 Pb-206 23.906 1.672 -8.393 0.734 0.800 9.652 3.485 Pb-205 23.809 0.838 -7.563 0.723 -0.427 8.655 2.204 Tl-208 24.100 0.000 -7.927 0.590 0.175 3.402 1.851 Tl-207 22.323 0.834 -9.200 0.665 1.500 4.518 3.358 Tl-206 24.082 0.000 -9.079 0.773 -0.964 9.821 1.490 Tl-205 23.809 0.838 -7.918 0.752 -0.589 9.758 2.220 Tl-204 23.713 0.000 -7.398 0.725 -1.368 7.903 1.181 Tl-203 23.616 0.842 -6.375 0.691 -0.679 7.871 1.964 Tl-202 23.519 0.000 -5.850 0.559 -0.361 3.582 2.150 --------------------------------------------------------- * Gamma-ray strength functions for Bi-210 E1: modified lorentzian model(MLO1)/5/ ER= 13.69 (MeV) EG= 3.85 (MeV) SIG= 330.00 (mb) M1: standard lorentzian model(SLO) ER= 6.90 (MeV) EG= 4.00 (MeV) SIG= 1.02 (mb) E2: standard lorentzian model(SLO) ER= 10.60 (MeV) EG= 3.59 (MeV) SIG= 5.44 (mb) References 1) O.Iwamoto, J. Nucl. Sci. Technol., 44, 687 (2007) 2) A.J.Koning and J.P.Delaroche, Nucl. Phys. A713, 231 (2003) 3) A. Gilbert and A.G.W. Cameron, Can. J. Phys, 43, 1446 (1965) 4) A. Mengoni and Y. Nakajima, J. Nucl. Sci. Technol., 31, 151 (1994) 5) V.A. Plujko et al., J. Nucl. Sci. Technol.(supp. 2), 811 (2002) 6) T.Kawano, K.Shibata, JAERI-Data/Code 97-037 (1997) in Japanese. 7) P.Oblozinsky et al.: BNL-91287-2010 (2010). 8) J.R.Huizenga and G.Igo, Nucl. Phys. 29,462 (1962)